ML20086H774
| ML20086H774 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/20/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H775 | List: |
| References | |
| AO-75-43, NUDOCS 8401200236 | |
| Download: ML20086H774 (2) | |
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June 20, 1975
/s N-Mr. A. Giambusso Director Division of Reactor Licensing Office of Nuclear Reactor Regulations Uni ted States Nuc lear Regulatory Corrrnis sion Washington, DC 20555
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region I, Office of Inspection and Enforcement, United States Nuclear Regulatory Corrrnission on June 12, 1975 written notification was made /
to Mr. Jcmes P. O'Reilly, Of fice of Inspection and Enforcement, Re gi or/1, United States Nuclear Regulatory Lommission on June 12, 1975 In accordance wi th Section 6.7.2. A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Peach Dottora Atomic Power Station, the following occurrence is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Reference:
License Number DPR lh Technical Specification
Reference:
3 7 0.1 Report No.:
50-277-75-43 Report Date:
June 20, 1975 Occurrence Date:
June 11, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pcnnsylvania 17314 Identification of Occurrence:
Leakage from feedwater check valve (6-968) outboard.
Condit_iens Price to Occurrence:
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unit.at approximately 67% power.
,f Description of Occurrence:
Late on June 11, 1975, water was found to be coming from the
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cluded positive identification of the source of the icokage. A sub-main steari isolation valve room onto the floor just outside.
On entry into this 'arca, the high thermal temperature and high radiation pre-sequent entry carly nn June 12, 1975, identified leakage from the
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piping insulation in the vicinity of outboard feedwater check valve
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50-277-75-43 June 20, 1973 Page 2 6-968.
Shortly after identifying the suspected leak, a normal plant shutdown was initiated to repair the leak. Upon plant shutdown, the insulation was removed from the ch2ck valve and the leakage was deter-mined to be coming from the valve bonnet joint.
Designation of Apparent Cause of Occurrence:
Tbc valve bonnet closure is scaled by a welded diaphragm.
Dye penetrant examination indicated a crack approximately 1 1/2" long in the bellows section of the seal plate at the 3 o' clock position (f acirg the reactor).
Analysis of Occurrence:
The safety implication of this occurrence is minimal since the inboard feedwater check valve (288) was recently tested (May 25, 1975) and found to leak through only 125 CC/ MIN. To further mitigate any impact from this occurrence, the plant was shutdown.
Corrective Action:
The seal plate was replaced in kind, the seal weld success-fully dye checked, the bonnet reinstalle<l and the closure Icak tested.
_F_ai lure Data:
None.
Very truly yours, k
M. [/. Cooney Ass't Gen'1 Superintendent Generation Division cc:
Mr. J. P. O'Reilly Director, Region 1 Of fice of Inspection and Enfcrcement United States Nuclear Regulatory Cormission 631 Perk Avenue King of Prussia, PA 19406
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